[Federal Register Volume 83, Number 89 (Tuesday, May 8, 2018)]
[Notices]
[Pages 20858-20866]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2018-09244]
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NUCLEAR REGULATORY COMMISSION
[NRC-2018-0085]
Biweekly Notice; Applications and Amendments to Facility
Operating Licenses and Combined Licenses Involving No Significant
Hazards Considerations
AGENCY: Nuclear Regulatory Commission.
ACTION: Biweekly notice.
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SUMMARY: Pursuant to Section 189a.(2) of the Atomic Energy Act of 1954,
as amended (the Act), the U.S. Nuclear Regulatory Commission (NRC) is
publishing this regular biweekly notice. The Act requires the
Commission to publish notice of any amendments issued, or proposed to
be issued, and grants the Commission the authority to issue and make
immediately effective any amendment to an operating license or combined
license, as applicable, upon a determination by the Commission that
such amendment involves no significant hazards consideration,
notwithstanding the pendency before the Commission of a request for a
hearing from any person.
This biweekly notice includes all notices of amendments issued, or
proposed to be issued, from April 10, 2018, to April 23, 2018. The last
biweekly notice was published on April 24, 2018.
DATES: Comments must be filed by June 7, 2018. A request for a hearing
must be filed by July 9, 2018.
ADDRESSES: You may submit comments by any of the following methods
(unless this document describes a different method for submitting
comments on a specific subject):
Federal Rulemaking Website: Go to http://www.regulations.gov and search for Docket ID NRC-2018-0085. Address
questions about NRC dockets to Jennifer Borges; telephone: 301-287-
9127; email: [email protected]. For technical questions, contact
the individual listed in the FOR FURTHER INFORMATION CONTACT section of
this document.
Mail comments to: May Ma, Office of Administration, Mail
Stop: TWFN-7-A60M, U.S. Nuclear Regulatory Commission, Washington, DC
20555-0001.
For additional direction on obtaining information and submitting
comments, see ``Obtaining Information and Submitting Comments'' in the
SUPPLEMENTARY INFORMATION section of this document.
FOR FURTHER INFORMATION CONTACT: Shirley Rohrer, U.S. Nuclear
Regulatory
[[Page 20859]]
Commission, Washington DC 20555-0001; telephone: 301-415-5411, email:
[email protected].
SUPPLEMENTARY INFORMATION:
I. Obtaining Information and Submitting Comments
A. Obtaining Information
Please refer to Docket ID NRC-2018-0085, facility name, unit
number(s), plant docket number, application date, and subject when
contacting the NRC about the availability of information for this
action. You may obtain publicly-available information related to this
action by any of the following methods:
Federal Rulemaking Website: Go to http://www.regulations.gov and search for Docket ID NRC-2018-0085.
NRC's Agencywide Documents Access and Management System
(ADAMS): You may obtain publicly-available documents online in the
ADAMS Public Documents collection at http://www.nrc.gov/reading-rm/adams.html. To begin the search, select ``ADAMS Public Documents'' and
then select ``Begin Web-based ADAMS Search.'' For problems with ADAMS,
please contact the NRC's Public Document Room (PDR) reference staff at
1-800-397-4209, 301-415-4737, or by email to [email protected]. The
ADAMS accession number for each document referenced (if it is available
in ADAMS) is provided the first time that it is mentioned in this
document
NRC's PDR: You may examine and purchase copies of public
documents at the NRC's PDR, Room O1-F21, One White Flint North, 11555
Rockville Pike, Rockville, Maryland 20852.
B. Submitting Comments
Please include Docket ID NRC-2018-0085, facility name, unit
number(s), plant docket number, application date, and subject in your
comment submission.
The NRC cautions you not to include identifying or contact
information that you do not want to be publicly disclosed in your
comment submission. The NRC will post all comment submissions at http://www.regulations.gov as well as enter the comment submissions into
ADAMS. The NRC does not routinely edit comment submissions to remove
identifying or contact information.
If you are requesting or aggregating comments from other persons
for submission to the NRC, then you should inform those persons not to
include identifying or contact information that they do not want to be
publicly disclosed in their comment submission. Your request should
state that the NRC does not routinely edit comment submissions to
remove such information before making the comment submissions available
to the public or entering the comment into ADAMS.
II. Notice of Consideration of Issuance of Amendments to Facility
Operating Licenses and Combined Licenses and Proposed No Significant
Hazards Consideration Determination
The Commission has made a proposed determination that the following
amendment requests involve no significant hazards consideration. Under
the Commission's regulations in Sec. 50.92 of title 10 of the Code of
Federal Regulations (10 CFR), this means that operation of the facility
in accordance with the proposed amendment would not: (1) Involve a
significant increase in the probability or consequences of an accident
previously evaluated; or (2) create the possibility of a new or
different kind of accident from any accident previously evaluated; or
(3) involve a significant reduction in a margin of safety. The basis
for this proposed determination for each amendment request is shown
below.
The Commission is seeking public comments on this proposed
determination. Any comments received within 30 days after the date of
publication of this notice will be considered in making any final
determination.
Normally, the Commission will not issue the amendment until the
expiration of 60 days after the date of publication of this notice. The
Commission may issue the license amendment before expiration of the 60-
day period provided that its final determination is that the amendment
involves no significant hazards consideration. In addition, the
Commission may issue the amendment prior to the expiration of the 30-
day comment period if circumstances change during the 30-day comment
period such that failure to act in a timely way would result, for
example in derating or shutdown of the facility. If the Commission
takes action prior to the expiration of either the comment period or
the notice period, it will publish in the Federal Register a notice of
issuance. If the Commission makes a final no significant hazards
consideration determination, any hearing will take place after
issuance. The Commission expects that the need to take this action will
occur very infrequently.
A. Opportunity To Request a Hearing and Petition for Leave To Intervene
Within 60 days after the date of publication of this notice, any
persons (petitioner) whose interest may be affected by this action may
file a request for a hearing and petition for leave to intervene
(petition) with respect to the action. Petitions shall be filed in
accordance with the Commission's ``Agency Rules of Practice and
Procedure'' in 10 CFR part 2. Interested persons should consult a
current copy of 10 CFR 2.309. The NRC's regulations are accessible
electronically from the NRC Library on the NRC's website at http://www.nrc.gov/reading-rm/doc-collections/cfr/. Alternatively, a copy of
the regulations is available at the NRC's Public Document Room, located
at One White Flint North, Room O1-F21, 11555 Rockville Pike (first
floor), Rockville, Maryland 20852. If a petition is filed, the
Commission or a presiding officer will rule on the petition and, if
appropriate, a notice of a hearing will be issued.
As required by 10 CFR 2.309(d) the petition should specifically
explain the reasons why intervention should be permitted with
particular reference to the following general requirements for
standing: (1) The name, address, and telephone number of the
petitioner; (2) the nature of the petitioner's right under the Act to
be made a party to the proceeding; (3) the nature and extent of the
petitioner's property, financial, or other interest in the proceeding;
and (4) the possible effect of any decision or order which may be
entered in the proceeding on the petitioner's interest.
In accordance with 10 CFR 2.309(f), the petition must also set
forth the specific contentions which the petitioner seeks to have
litigated in the proceeding. Each contention must consist of a specific
statement of the issue of law or fact to be raised or controverted. In
addition, the petitioner must provide a brief explanation of the bases
for the contention and a concise statement of the alleged facts or
expert opinion which support the contention and on which the petitioner
intends to rely in proving the contention at the hearing. The
petitioner must also provide references to the specific sources and
documents on which the petitioner intends to rely to support its
position on the issue. The petition must include sufficient information
to show that a genuine dispute exists with the applicant or licensee on
a material issue of law or fact. Contentions must be limited to matters
within the scope of the proceeding. The contention must be one which,
if proven, would entitle the
[[Page 20860]]
petitioner to relief. A petitioner who fails to satisfy the
requirements at 10 CFR 2.309(f) with respect to at least one contention
will not be permitted to participate as a party.
Those permitted to intervene become parties to the proceeding,
subject to any limitations in the order granting leave to intervene.
Parties have the opportunity to participate fully in the conduct of the
hearing with respect to resolution of that party's admitted
contentions, including the opportunity to present evidence, consistent
with the NRC's regulations, policies, and procedures.
Petitions must be filed no later than 60 days from the date of
publication of this notice. Petitions and motions for leave to file new
or amended contentions that are filed after the deadline will not be
entertained absent a determination by the presiding officer that the
filing demonstrates good cause by satisfying the three factors in 10
CFR 2.309(c)(1)(i) through (iii). The petition must be filed in
accordance with the filing instructions in the ``Electronic Submissions
(E-Filing)'' section of this document.
If a hearing is requested, and the Commission has not made a final
determination on the issue of no significant hazards consideration, the
Commission will make a final determination on the issue of no
significant hazards consideration. The final determination will serve
to establish when the hearing is held. If the final determination is
that the amendment request involves no significant hazards
consideration, the Commission may issue the amendment and make it
immediately effective, notwithstanding the request for a hearing. Any
hearing would take place after issuance of the amendment. If the final
determination is that the amendment request involves a significant
hazards consideration, then any hearing held would take place before
the issuance of the amendment unless the Commission finds an imminent
danger to the health or safety of the public, in which case it will
issue an appropriate order or rule under 10 CFR part 2.
A State, local governmental body, Federally-recognized Indian
Tribe, or agency thereof, may submit a petition to the Commission to
participate as a party under 10 CFR 2.309(h)(1). The petition should
state the nature and extent of the petitioner's interest in the
proceeding. The petition should be submitted to the Commission no later
than 60 days from the date of publication of this notice. The petition
must be filed in accordance with the filing instructions in the
``Electronic Submissions (E-Filing)'' section of this document, and
should meet the requirements for petitions set forth in this section,
except that under 10 CFR 2.309(h)(2) a State, local governmental body,
or Federally-recognized Indian Tribe, or agency thereof does not need
to address the standing requirements in 10 CFR 2.309(d) if the facility
is located within its boundaries. Alternatively, a State, local
governmental body, Federally-recognized Indian Tribe, or agency thereof
may participate as a non-party under 10 CFR 2.315(c). If a hearing is
granted, any person who is not a party to the proceeding and is not
affiliated with or represented by a party may, at the discretion of the
presiding officer, be permitted to make a limited appearance pursuant
to the provisions of 10 CFR 2.315(a). A person making a limited
appearance may make an oral or written statement of his or her position
on the issues but may not otherwise participate in the proceeding. A
limited appearance may be made at any session of the hearing or at any
prehearing conference, subject to the limits and conditions as may be
imposed by the presiding officer. Details regarding the opportunity to
make a limited appearance will be provided by the presiding officer if
such sessions are scheduled.
B. Electronic Submissions (E-Filing)
All documents filed in NRC adjudicatory proceedings, including a
request for hearing and petition for leave to intervene (petition), any
motion or other document filed in the proceeding prior to the
submission of a request for hearing or petition to intervene, and
documents filed by interested governmental entities that request to
participate under 10 CFR 2.315(c), must be filed in accordance with the
NRC's E-Filing rule (72 FR 49139; August 28, 2007, as amended at 77 FR
46562; August 3, 2012). The E-Filing process requires participants to
submit and serve all adjudicatory documents over the internet, or in
some cases to mail copies on electronic storage media. Detailed
guidance on making electronic submissions may be found in the Guidance
for Electronic Submissions to the NRC and on the NRC website at http://www.nrc.gov/site-help/e-submittals.html. Participants may not submit
paper copies of their filings unless they seek an exemption in
accordance with the procedures described below.
To comply with the procedural requirements of E-Filing, at least 10
days prior to the filing deadline, the participant should contact the
Office of the Secretary by email at [email protected], or by
telephone at 301-415-1677, to (1) request a digital identification (ID)
certificate, which allows the participant (or its counsel or
representative) to digitally sign submissions and access the E-Filing
system for any proceeding in which it is participating; and (2) advise
the Secretary that the participant will be submitting a petition or
other adjudicatory document (even in instances in which the
participant, or its counsel or representative, already holds an NRC-
issued digital ID certificate). Based upon this information, the
Secretary will establish an electronic docket for the hearing in this
proceeding if the Secretary has not already established an electronic
docket.
Information about applying for a digital ID certificate is
available on the NRC's public website at http://www.nrc.gov/site-help/e-submittals/getting-started.html. Once a participant has obtained a
digital ID certificate and a docket has been created, the participant
can then submit adjudicatory documents. Submissions must be in Portable
Document Format (PDF). Additional guidance on PDF submissions is
available on the NRC's public website at http://www.nrc.gov/site-help/electronic-sub-ref-mat.html. A filing is considered complete at the
time the document is submitted through the NRC's E-Filing system. To be
timely, an electronic filing must be submitted to the E-Filing system
no later than 11:59 p.m. Eastern Time on the due date. Upon receipt of
a transmission, the E-Filing system time-stamps the document and sends
the submitter an email notice confirming receipt of the document. The
E-Filing system also distributes an email notice that provides access
to the document to the NRC's Office of the General Counsel and any
others who have advised the Office of the Secretary that they wish to
participate in the proceeding, so that the filer need not serve the
document on those participants separately. Therefore, applicants and
other participants (or their counsel or representative) must apply for
and receive a digital ID certificate before adjudicatory documents are
filed so that they can obtain access to the documents via the E-Filing
system.
A person filing electronically using the NRC's adjudicatory E-
Filing system may seek assistance by contacting the NRC's Electronic
Filing Help Desk through the ``Contact Us'' link located on the NRC's
public website at http://www.nrc.gov/site-help/e-submittals.html, by
email to [email protected], or by a toll-free call at 1-866-672-
7640. The NRC
[[Page 20861]]
Electronic Filing Help Desk is available between 9 a.m. and 6 p.m.,
Eastern Time, Monday through Friday, excluding government holidays.
Participants who believe that they have a good cause for not
submitting documents electronically must file an exemption request, in
accordance with 10 CFR 2.302(g), with their initial paper filing
stating why there is good cause for not filing electronically and
requesting authorization to continue to submit documents in paper
format. Such filings must be submitted by: (1) First class mail
addressed to the Office of the Secretary of the Commission, U.S.
Nuclear Regulatory Commission, Washington, DC 20555-0001, Attention:
Rulemaking and Adjudications Staff; or (2) courier, express mail, or
expedited delivery service to the Office of the Secretary, 11555
Rockville Pike, Rockville, Maryland 20852, Attention: Rulemaking and
Adjudications Staff. Participants filing adjudicatory documents in this
manner are responsible for serving the document on all other
participants. Filing is considered complete by first-class mail as of
the time of deposit in the mail, or by courier, express mail, or
expedited delivery service upon depositing the document with the
provider of the service. A presiding officer, having granted an
exemption request from using E-Filing, may require a participant or
party to use E-Filing if the presiding officer subsequently determines
that the reason for granting the exemption from use of E-Filing no
longer exists.
Documents submitted in adjudicatory proceedings will appear in the
NRC's electronic hearing docket which is available to the public at
https://adams.nrc.gov/ehd, unless excluded pursuant to an order of the
Commission or the presiding officer. If you do not have an NRC-issued
digital ID certificate as described above, click cancel when the link
requests certificates and you will be automatically directed to the
NRC's electronic hearing dockets where you will be able to access any
publicly available documents in a particular hearing docket.
Participants are requested not to include personal privacy information,
such as social security numbers, home addresses, or personal phone
numbers in their filings, unless an NRC regulation or other law
requires submission of such information. For example, in some
instances, individuals provide home addresses in order to demonstrate
proximity to a facility or site. With respect to copyrighted works,
except for limited excerpts that serve the purpose of the adjudicatory
filings and would constitute a Fair Use application, participants are
requested not to include copyrighted materials in their submission.
For further details with respect to these license amendment
applications, see the application for amendment which is available for
public inspection in ADAMS and at the NRC's PDR. For additional
direction on accessing information related to this document, see the
``Obtaining Information and Submitting Comments'' section of this
document.
Exelon Generation Company, LLC, Docket Nos. 50-317 and 50-318, Calvert
Cliffs Nuclear Power Plant (CCNPP), Unit Nos. 1 and 2, Calvert County,
Maryland
Exelon Generation Company, LLC, Docket Nos. 50-220 and 50-410, Nine
Mile Point Nuclear Station (NMP), Unit Nos. 1 and 2, Oswego County, New
York
Exelon Generation Company, LLC, Docket No. 50-244, R.E. Ginna Nuclear
Power Plant (Ginna), Wayne County, New York
Date of amendment request: March 26, 2018. A publicly-available
version is in ADAMS under Accession No. ML18086A138.
Description of amendment request: The amendments would revise the
licenses to eliminate the Nuclear Advisory Committee.
Basis for proposed no significant hazards consideration
determination: As required by 10 CFR 50.91(a), the licensee has
provided its analysis of the issue of no significant hazards
consideration, which is presented below:
1. Does the proposed amendment involve a significant increase in
the probability or consequences of an accident previously evaluated?
Response: No.
The proposed amendment deletes license conditions associated
with the establishment of the Nuclear Advisory Committee (NAC) as
provided in the orders approving the corporate merger between Exelon
Corporation and Constellation Energy Group, Inc., and the resultant
transfer of the renewed facility operating licenses for CCNPP, Units
1 and 2; NMP, Units 1 and 2; and Ginna on February 15, 2012.
The NAC's oversight function helps to ensure that Constellation
Energy Nuclear Group (CENG) remains in compliance with laws and
regulations regarding foreign domination and control of nuclear
operations, and that a decision of a foreign government could not
adversely affect or interfere with the reliable and safe operation
of any nuclear assets of CENG or its affiliates.
The NAC is an advisory committee and does not function in a
decision-making role. If the NAC becomes aware of a Foreign
Ownership, Control, or Domination (FOCD) event or issue, it will
bring it to the attention of CENG management and/or the CENG Board
of Directors. The NAC advises the CENG Board of Directors and
provides its recommendations regarding the regulatory or safety
significance of the issue, and recommended actions to address the
issue.
Eliminating the NAC will not impact compliance with FOCD
requirements, nor will it impair the ability to identify and resolve
any FOCD issues that could impact the safe or reliable operation of
the nuclear units. Multiple avenues exist to resolve any concerns
regarding FOCD issues. These include the ability of personnel to
report an FOCD concern to their supervisor, enter a potential FOCD
concern into the corrective action program, or raise the concern
with the Employee Concerns Program. In addition, personnel are
always free to report any concern directly to the NRC.
This proposed administrative change enables the elimination of
the NAC and does not alter: 1) The extent of the ownership of the
reactors, 2) the authority to operate the reactors, 3) the directors
or officers and details concerning the relevant companies, 4) access
to restricted data, or; 5) details concerning ownership of the
foreign parent company. This change does not alter compliance with
the Atomic Energy Act, 10 CFR 50.38, ``Ineligibility of Certain
Applicants,'' or the guidance provided in the Standard Review Plan
(SRP), Final Standard Review Plan on Foreign Ownership, Control, or
Domination. Additionally, this administrative change will not impact
reactor operations or safety analyses.
Therefore, the proposed change does not involve a significant
increase in the probability or consequences of an accident
previously evaluated.
2. Does the proposed amendment create the possibility of a new
or different kind of accident from any accident previously
evaluated?
Response: No.
This proposed administrative change enables the elimination of
the NAC and does not alter: 1) The extent of the ownership of the
reactors, 2) the authority to operate the reactors, 3) the directors
or officers and details concerning the relevant companies, 4) access
to restricted data, or; 5) details concerning ownership of the
foreign parent company. This change does not alter compliance with
the Atomic Energy Act, 10 CFR 50.38, ``Ineligibility of Certain
Applicants,'' or the guidance provided in the Standard Review Plan
(SRP), Final Standard Review Plan on Foreign Ownership, Control, or
Domination.
Eliminating the NAC will not impact compliance with FOCD
requirements, nor will it impair the ability to identify and resolve
any FOCD issues that could impact the safe or reliable operation of
the nuclear units. FOCD issues will be addressed via current
processes (employees reporting to their supervisor, entering an
issue into the corrective action program, raising the concern to the
Employee Concerns Program, or reporting directly to the NRC).
This is an administrative change, and no new operating
configuration is being imposed that would create a new failure
[[Page 20862]]
scenario. In addition, no new failure modes are being created for
any plant equipment. This change does not result in any new or
different accident scenarios.
Therefore, the proposed change does not create the possibility
of a new or different kind of accident from any previously
evaluated.
3. Does the proposed amendment involve a significant reduction
in a margin of safety?
Response: No.
This is an administrative change. No safety analyses are being
changed or modified as a result of this proposed change. This
proposed administrative change does not alter the manner in which
safety limits, limiting safety system settings, or limiting
conditions for operation are determined. Margins associated with the
current safety analyses acceptance criteria are unaffected. The
safety systems credited in the safety analyses will continue to be
available to perform their mitigation functions.
Therefore, the proposed change does not result in a significant
reduction in a margin of safety.
The NRC staff has reviewed the licensee's analysis and, based on
this review, it appears that the three standards of 10 CFR 50.92(c) are
satisfied. Therefore, the NRC staff proposes to determine that the
requested amendments involve no significant hazards consideration.
Attorney for licensee: Tamra Domeyer, Associate General Counsel,
Exelon Generation Company, LLC, 4300 Winfield Road, Warrenville, IL
60555.
NRC Branch Chief: David J. Wrona.
Indiana Michigan Power Company, Docket No. 50-315, Donald C. Cook
Nuclear Plant (CNP), Unit No. 1, Berrien County, Michigan
Date of amendment request: March 7, 2018. A publicly-available
version is in ADAMS under Accession No. ML18072A012.
Description of amendment request: The proposed change would allow
for the application of leak-before-break (LBB) methodology to piping
for the accumulator, residual heat removal, and safety injection
systems at the CNP, Unit No. 1. In addition, the proposed change would
modify technical specification (TS) 3.4.13, ``RCS [Reactor Coolant
System] Operational LEAKAGE.''
Basis for proposed no significant hazards consideration
determination: As required by 10 CFR 50.91(a), the licensee has
provided its analysis of the issue of no significant hazards
consideration, which is presented below:
1. Does the proposed amendment involve a significant increase in
the probability or consequences of an accident previously evaluated?
Response: No.
Overall protection system performance will remain within the
bounds of the previously performed accident analyses. The design of
the protection systems will be unaffected. The reactor protection
system and engineered safety feature actuation system will continue
to function in a manner consistent with the plant design basis. All
design, material and construction standards that were applicable
prior to the request are maintained.
For CNP, Unit 1, the bounding accident for pipe breaks is a
Large Break Loss of Coolant Accident (LBLOCA). Since the application
of the LBB analysis verifies the integrity of the piping attached to
the reactor coolant system, the probability of a previously
evaluated accident is not increased. The consequences of a LBLOCA
have been previously evaluated and found to be acceptable. The
application of the LBB analysis will cause no change in the dose
analysis associated with a LBLOCA, and therefore, does not affect
the consequences of an accident.
The proposed amendment will not alter any assumptions or change
any mitigation actions in the radiological consequence evaluations
in the Updated Final Safety Analysis Report (UFSAR).
Therefore, the proposed changes do not involve a significant
increase in the probability or consequences of an accident
previously evaluated.
2. Does the proposed amendment create the possibility of a new
or different kind of accident from any previously evaluated?
Response: No.
No new accident scenarios, failure mechanisms, or single
failures are introduced as a result of the proposed change. All
systems, structures, and components previously required for the
mitigation of an event remain capable of fulfilling their intended
design function. The proposed change has no adverse effects on any
safety related systems or components and does not challenge the
performance or integrity of any safety related system. Further,
there are no changes in the method by which any safety-related plant
system performs its safety function. This amendment will not affect
the normal method of power operation or change any operating
parameters.
Therefore, the proposed changes do not create the possibility of
a new or different kind of accident from any accident previously
evaluated.
3. Does the proposed amendment involve a significant reduction
in a margin of safety?
Response: No.
Margin of safety is related to the ability of the fission
product barriers to perform their design functions during and
following accident conditions. These barriers include the fuel
cladding, the reactor coolant system, and the containment. The
proposed amendment request does not involve a change to any of these
barriers.
The proposed change does not involve a significant reduction in
a margin of safety because the proposed changes do not reduce the
margin of safety that exists in the present CNP Unit 1 TS or UFSAR.
The operability requirements of the TS are consistent with the
initial condition assumptions of the safety analyses.
This proposed amendment uses LBB technology combined with
leakage monitoring to show that it is acceptable to exclude the
dynamic effects associated with postulated pipe ruptures from the
licensing basis for the systems evaluated that are attached to the
RCS. The enclosed analysis demonstrates that the LBB margins
discussed in NUREG-1061, Volume 3 are satisfied.
Therefore, the proposed changes do not involve a significant
reduction in a margin of safety.
The NRC staff has reviewed the licensee's analysis and, based on
this review, it appears that the three standards of 10 CFR 50.92(c) are
satisfied. Therefore, the NRC staff proposes to determine that the
amendment request involves no significant hazards consideration.
Attorney for licensee: Robert B. Haemer, Senior Nuclear Counsel,
One Cook Place, Bridgman, MI 49106.
NRC Branch Chief: David J. Wrona.
Tennessee Valley Authority (TVA), Docket No. 50-259, Browns Ferry
Nuclear Plant (BFN), Unit 1, Limestone County, Alabama
Date of amendment request: March 16, 2018, as supplemented by
letter dated April 19, 2018. Publicly-available versions are in ADAMS
under Accession Nos. ML18080A171 and ML18109A573.
Description of amendment request: The amendment would revise
License Condition 2.C(18)(a)3 for Unit 1 that requires the submittal of
a revised Unit 1 replacement steam dryer (RSD) analysis utilizing the
Unit 3 on-dryer strain gauge based end-to-end bias and uncertainties at
extended power conditions ``at least 90 days prior to the start of the
BFN Unit 1 EPU [extended power uprate] outage.'' TVA is unable to
submit the revised Unit 1 RSD analysis 90 days prior to the start of
the Unit 1 EPU outage, because of delays in Unit 3 power ascension. In
its supplement dated April 19, 2018, TVA proposed to revise Unit 1
analysis submittal from 90 days before the outage to 60 days prior to
exceeding 3458 megawatt thermal (MWt) after the outage. The license
amendment request was originally noticed in the Federal Register on
April 10, 2018 (83 FR 15418). The renotice replaces and supersedes the
original notice in its entirety.
Basis for proposed no significant hazards consideration
determination: As required by 10 CFR 50.91(a), the licensee has
provided its analysis of the issue of no significant hazards
consideration, which is presented below.
1. Does the proposed amendment involve a significant increase in
the probability or consequence of an accident previously evaluated?
Response: No.
[[Page 20863]]
The proposed license amendment reduces the length of time, from
90 days prior to the outage to 60 days prior to exceeding 3458 MWt
after the outage, by which a revised analysis of the Browns Ferry
Nuclear Plant (BFN) Unit 1 replacement steam dryer (RSD), performed
using an NRC-approved methodology benchmarked on the BFN Unit 3 RSD,
must be submitted to the NRC for information. There is no required
review or approval of the revised analysis needed to satisfy the
license condition. The proposed change is an administrative change
to the period before the outage and does not impact any system,
structure or component in such a way as to affect the probability or
consequences of an accident previously evaluated. The proposed
amendment is purely administrative and has no technical or safety
aspects. Therefore, the proposed change does not involve a
significant increase in the probability or consequences of an
accident previously evaluated.
2. Does the proposed amendment create the possibility of a new
or different kind of accident from any accident previously
evaluated?
Response: No.
The proposed license amendment reduces the length of time, from
90 days prior to the outage to 60 days prior to exceeding 3458 MWt
after the outage, by which a revised analysis of the BFN Unit 1 RSD
must be submitted to the NRC for information. The proposed amendment
is purely administrative and has no technical or safety aspects.
Therefore, the proposed change does not create the possibility of a
new or different kind of accident from any accident previously
evaluated.
3. Does the proposed amendment involve a significant reduction
in a margin of safety?
Response: No.
The proposed license amendment reduces the length of time, from
90 days prior to the outage to 60 days prior to exceeding 3458 MWt
after the outage, by which a revised analysis of the BFN Unit 1 RSD
must be submitted to the NRC for information. The proposed amendment
is purely administrative and has no technical or safety aspects.
Therefore, the proposed change does not involve a significant
reduction in a margin of safety.
The NRC staff has reviewed the licensee's analysis and, based on
this review, it appears that the three standards of 10 CFR 50.92(c) are
satisfied. Therefore, the NRC staff proposes to determine that the
amendment request involves no significant hazards consideration.
Attorney for licensee: General Counsel, Tennessee Valley Authority,
400 West Summit Hill Drive, 6A West Tower, Knoxville, TN 37902.
NRC Acting Branch Chief: Brian W. Tindell.
United States Maritime Administration (MARAD), Docket No. 50-238,
Nuclear Ship Savannah (NSS), Baltimore, Maryland
Date of amendment request: March 30, 2018. A publicly-available
version is in ADAMS under Accession No. ML18093A377.
Description of amendment request: The proposed amendment would
amend the Technical Specifications to establish controls for all
accesses to the Containment Vessel (CV) in support of two structural
modifications. One modification will construct a horizontal access
portal to the CV that will be secured by a new D Deck CV Door. The
other modification will restore the original forward access between the
Cold Chemistry Laboratory (CCL) at D Deck and the Reactor Compartment
(RC) Lower Level.
Basis for proposed no significant hazards consideration
determination: As required by 10 CFR 50.91(a), the licensee has
provided its analysis of the issue of no significant hazards
consideration, which is presented below:
1. Does the proposed amendment involve a significant increase in
the probability or consequences of an accident previously evaluated?
Response: No.
The proposed changes will modify the Technical Specifications
(TSs) to include all CV accesses into TS 3.7.1.1 and add two
additional accesses into TS 3.7.1.5. The proposed changes are
required by two modifications to plant equipment. The completed
modification improved personnel access to the RC Lower Level by
restoring access between the CCL at D Deck and the RC Lower Level
and the proposed modification will improve personnel access to the
CV by constructing a horizontal access portal that will be secured
by the D Deck CV Door. Neither the proposed changes to the TSs nor
the modifications that require those changes affect basic plant
operation of a permanently shutdown and defueled facility.
The completed modification restored the original forward access
between the CCL at D Deck and the RC Lower Level to improve normal
personnel access to the RC Lower Level. It also improved the ability
to remove an injured person from the RC Lower Level.
Prior to completing the modification, the only access to the RC
Lower Level was via a 12 in. radius access trunk down an
approximately 36 ft. ladder from B Deck of the RC to the RC Lower
Level at the Tank Top. Emergency personnel egress from the RC Lower
Level will be available through either the D Deck opening or the 12
in. radius access trunk down an approximately 36 ft. ladder from B
Deck of the RC to the RC Lower Level at the Tank Top.
This modification effectively expanded the boundary of the RC to
include the CCL and therefore, requires the proposed change to TS
3.7.1.5 to include the C Deck entrance to the CCL.
The proposed modification--to construct a horizontal access
portal that will be secured by the D Deck CV Door--is an improvement
in personnel safety. Emergency personnel egress from the CV, in
addition to that provided by existing ladders, will be available
through the open D Deck CV Door.
The proposed modification will add an access to the CV that has
not previously existed and therefore, requires the proposed change
to TS 3.7.1.5 to include the D Deck CV Door. Note that this door
will open into a passageway similar to the B Beck RC door that is
currently the only door listed in TS 3.7.1.5. However, since the
proposed D Deck CV Door will provide a direct access to the CV, a
change is also proposed to TS 3.7.1.1 to include all CV entrances
into its scope.
If any event requires shutting any door to the CV or RC, the
limiting closure time is the time it would take for the door guard
to simply swing the door shut and secure it with installed dogs or
quick closure operators. The worst case time to secure any door is
the time to secure the D Deck CV Door, a watertight double door. The
time to secure it is estimated to be approximately 120 seconds after
the CV and RC have been checked to be free of personnel.
Administrative controls will be put in place to ensure that (1) the
swing path of the door is not blocked, (2) the door shall not be
fouled and (3) trained personnel will be in the immediate vicinity
of the door and available to close it in a timely manner following
any event where closing the door is appropriate.
The NSS's reactor is not operational and the level of
radioactivity in the NSS has significantly decreased from the levels
that existed when the 1976 Possession-only License was issued. No
aspect of any of the proposed changes is an initiator of any
accident previously evaluated. Consequently, the probability of an
accident previously evaluated is not significantly increased.
Therefore, the proposed changes do not involve a significant
increase in the probability or consequences of an accident
previously evaluated.
2. Does the proposed amendment create the possibility of a new
or different kind of accident from any accident previously
evaluated?
Response: No.
The proposed changes will modify the Technical Specifications
(TSs) to include all CV accesses into TS 3.7.1.1 and add two
additional accesses into TS 3.7.1.5. The proposed changes are
required by two modifications to plant equipment. The completed
modification improved personnel access to the RC Lower Level by
restoring access between the CCL at D Deck and the RC Lower Level
and the proposed modification will improve personnel access to the
CV by constructing a horizontal access portal that will be secured
by the D Deck CV Door. Neither the proposed changes to the TSs nor
the modifications that require those changes affect basic plant
operation of a permanently shutdown and defueled facility.
In both cases, the physical alteration of plant equipment is
similar to that which was previously allowed by Technical
Specifications. Specifically, since November
[[Page 20864]]
1995, the C Deck Door to the Cold Chemistry Laboratory has been
locked from the outside and fitted with an intrusion alarm that
alerts a security monitoring station. When opened, the door has been
manned and protected. Likewise, the D Deck CV Door shall be locked
from the outside and fitted with an intrusion alarm that alerts a
security monitoring station; when opened the D Deck CV Door shall be
manned and protected.
Neither of the proposed changes to TS 3.7.1.1 and TS 3.7.1.5
will change the method by which any safety-related system performs
its function. As such, no new or different types of equipment will
be installed, and the basic operation of installed equipment is
unchanged. The methods governing plant operation and testing remain
consistent with current safety analysis assumptions.
Therefore, the proposed changes do not create the possibility of
a new or different kind of accident from any previously evaluated.
3. Does the change involve a significant reduction in a margin
of safety?
Response: No.
The proposed changes will modify the Technical Specifications
(TSs) to include all CV accesses into TS 3.7.1.1 and add two
additional accesses into TS 3.7.1.5. The proposed changes are
required by two modifications to plant equipment. The completed
modification improved personnel access to the RC Lower Level by
restoring access between the CCL at D Deck and the RC Lower Level
and the proposed modification will improve personnel access to the
CV by constructing a horizontal access portal that will be secured
by the D Deck CV Door. Neither the proposed changes to the TSs nor
the modifications that require those changes affect any margins of
safety that are relevant to the ship's defueled and partially
dismantled reactor.
The completed modification improved personnel access to the RC
Lower Level by restoring access between the CCL at D Deck and the RC
Lower Level. The proposed modification will improve personnel access
to the CV by constructing a horizontal access portal that will be
secured by the D Deck CV Door.
As such, there are no changes being made to safety analysis
assumptions, safety limits or safety system settings that would
adversely affect plant safety or are relevant to the ship's defueled
and partially dismantled reactor as a result of the proposed
changes.
Additionally, when any door to the CV or RC door is open,
administrative controls will be put in place to ensure that (1) the
swing path of the door is not blocked, (2) the door shall not be
fouled and (3) trained personnel will be in the immediate vicinity
of the door and available to close it in a timely manner following
any event where closing the door is appropriate.
Therefore, the proposed changes do not involve a significant
reduction in a margin of safety.
The NRC staff has reviewed the licensee's analysis and, based on
this review, it appears that the three standards of 10 CFR 50.92(c) are
satisfied. Therefore, the NRC staff proposes to determine that the
amendment request involves no significant hazards consideration.
Advisor for licensee: Erhard W. Koehler, U.S. Department of
Transportation, Maritime Administration, 1200 New Jersey Ave. SE,
Washington, DC 20590.
NRC Branch Chief: Bruce Watson.
III. Notice of Issuance of Amendments to Facility Operating Licenses
and Combined Licenses
During the period since publication of the last biweekly notice,
the Commission has issued the following amendments. The Commission has
determined for each of these amendments that the application complies
with the standards and requirements of the Atomic Energy Act of 1954,
as amended (the Act), and the Commission's rules and regulations. The
Commission has made appropriate findings as required by the Act and the
Commission's rules and regulations in 10 CFR chapter I, which are set
forth in the license amendment.
A notice of consideration of issuance of amendment to facility
operating license or combined license, as applicable, proposed no
significant hazards consideration determination, and opportunity for a
hearing in connection with these actions, was published in the Federal
Register as indicated.
Unless otherwise indicated, the Commission has determined that
these amendments satisfy the criteria for categorical exclusion in
accordance with 10 CFR 51.22. Therefore, pursuant to 10 CFR 51.22(b),
no environmental impact statement or environmental assessment need be
prepared for these amendments. If the Commission has prepared an
environmental assessment under the special circumstances provision in
10 CFR 51.22(b) and has made a determination based on that assessment,
it is so indicated.
For further details with respect to the action see (1) the
applications for amendment, (2) the amendment, and (3) the Commission's
related letter, Safety Evaluation, and/or Environmental Assessment, as
indicated. All of these items can be accessed as described in the
``Obtaining Information and Submitting Comments'' section of this
document.
Duke Energy Carolinas, LLC, Docket Nos. 50-269, 50-270, and 50-287,
Oconee Nuclear Station, Unit Nos. 1, 2, and 3, Oconee County, South
Carolina
Date of amendment request: March 30, 2017, as supplemented by
letters dated May 11 and October 16, 2017, and April 4, 2018.
Brief description of amendments: The amendments revised the
Technical Specifications in accordance with the NRC-approved Technical
Specifications Task Force (TSTF) Standard Technical Specifications
Change Traveler TSTF-448, Revision 3, ``Control Room Habitability,''
with variations from TSTF-448 because of the plant's design and
licensing basis.
Date of issuance: April 12, 2018.
Effective date: As of the date of issuance and shall be implemented
within 180 days of issuance.
Amendment Nos.: 408, 410, and 409. A publicly-available version is
in ADAMS under Accession No. ML18040A194; documents related to these
amendments are listed in the Safety Evaluation enclosed with the
amendments.
Facility Operating License Nos. DPR-38, DPR-47 and DPR-55:
Amendments revised the Facility Operating Licenses and Technical
Specifications.
Date of initial notice in Federal Register: July 18, 2017 (82 FR
32879). The supplemental letters dated October 16, 2017, and April 4,
2018, provided additional information that clarified the application,
did not expand the scope of the application as originally noticed, and
did not change the NRC staff's original proposed no significant hazards
consideration determination as published in the Federal Register.
The Commission's related evaluation of the amendment is contained
in a Safety Evaluation dated April 12, 2018.
No significant hazards consideration comments received: No.
Duke Energy Progress Inc., Docket No. 50-261, H.B. Robinson Steam
Electric Plant, Unit No. 2 (Robinson), Darlington County, South
Carolina
Duke Energy Progress, LLC, Docket No. 50-400, Shearon Harris Nuclear
Power Plant, Unit 1 (Harris), Wake and Chatham Counties, North Carolina
Date of amendment request: November 19, 2015, as superseded by
application dated October 3, 2016, and as supplemented by letters dated
November 10, 2016, and October 9, October 30, and December 19, 2017.
Brief description of amendments: The amendments revised the
Robinson Technical Specification (TS) 5.6.5.b and the Harris TS
6.9.1.6.2 to adopt the methodology reports DPC-NE-3008-P, Revision 0,
``Thermal-Hydraulic Models for Transient Analysis,'' and DPC-NE-3009-P,
Revision 0, ``FSAR/UFSAR Chapter 15 Transient Analysis Methodology,''
for application specific to Robinson and Harris.
[[Page 20865]]
Date of issuance: April 10, 2018.
Effective date: As of the date of issuance and shall be implemented
within 120 days of issuance.
Amendment Nos.: 164 (Robinson) and 257 (Harris). A publicly-
available version is in ADAMS under Accession No. ML18060A401;
documents related to these amendments are listed in the Safety
Evaluation enclosed with the amendments.
Renewed Facility Operating License Nos. DPR-23 and NPF-63:
Amendments revised the Facility Operating Licenses and TSs.
Date of initial notice in Federal Register: April 5, 2016 (81 FR
19645). The supplemental letter dated October 3, 2016, provided
additional information that expanded the scope of the application as
originally noticed, and changed the NRC staff's original proposed no
significant hazards consideration determination as published in the
Federal Register. Accordingly, the NRC published a second proposed no
significant hazards consideration determination in the Federal Register
on May 2, 2017 (82 FR 20496). This notice superseded the original
notice in its entirety. The supplemental letters dated November 10,
2016, and October 9, October 30, and December 19, 2017, provided
additional information that clarified the application, did not expand
the scope beyond the second notice, and did not change the NRC staff's
proposed no significant hazards consideration determination as
published in the Federal Register.
The Commission's related evaluations of the amendments are
contained in the Safety Evaluation dated April 10, 2018.
No significant hazards consideration comments received: No.
Duke Energy Progress, LLC, Docket Nos. 50-325 and 50-324, Brunswick
Steam Electric Plant, Unit Nos. 1 and 2 (Brunswick), Brunswick County,
North Carolina
Date of amendment request: June 29, 2017, as supplemented by
letters dated January 4 and January 23, 2018.
Brief description of amendments: The amendments adopted Technical
Specifications Task Force (TSTF) Traveler TSTF-542, Revision 2,
``Reactor Pressure Vessel Water Inventory Control [RPVWIC].'' The
amendments replaced existing technical specification (TS) requirements
associated with ``operations with the potential for draining the
reactor vessel,'' with revised TSs providing alternative requirements
for RPVWIC. These alternative requirements protect Safety Limit
2.1.1.3, which states, ``Reactor vessel water level shall be greater
than the top of active irradiated fuel.''
Date of issuance: April 13, 2018.
Effective date: As of the date of issuance and shall be
implemented: (1) For Unit 1, within 180 days of issuance and (2) for
Unit 2, prior to its 2019 refueling outage.
Amendment Nos.: 283 (Unit No. 1) and 311 (Unit No. 2). A publicly-
available version is in ADAMS under Accession No. ML18039A444;
documents related to these amendments are listed in the Safety
Evaluation enclosed with the amendments.
Renewed Facility Operating License Nos. DPR-71 and DPR-62:
Amendments revised the Renewed Facility Operating Licenses and TSs.
Date of initial notice in Federal Register: September 12, 2017 (82
FR 42846). The supplemental letters dated January 4 and January 23,
2018, provided additional information that clarified the application,
did not expand the scope of the application as originally noticed, and
did not change the NRC staff's original proposed no significant hazards
consideration determination as published in the Federal Register.
The Commission's related evaluation of the amendments is contained
in a Safety Evaluation dated April 13, 2018.
No significant hazards consideration comments received: No.
Energy Northwest, Docket No. 50-397, Columbia Generating Station,
Benton County, Washington
Date of amendment request: August 30, 2016, as supplemented by
letter dated November 20, 2017.
Brief description of amendment: The amendment revised the Columbia
Generating Station Final Safety Analysis Report to reclassify reactor
water cleanup piping, valves, pumps, and mechanical modules located
outside of the primary and secondary containment in the radwaste
building from Quality Group C to Quality Group D.
Date of issuance: April 17, 2018.
Effective date: As of its date of issuance and shall be implemented
within 120 days from the date of issuance.
Amendment No.: 248. A publicly-available version is in ADAMS under
Accession No. ML18075A351; documents related to this amendment are
listed in the Safety Evaluation enclosed with the amendment.
Renewed Facility Operating License No. NPF-21: The amendment
revised the Final Safety Analysis Report.
Date of initial notice in Federal Register: December 6, 2016 (81 FR
87968). The supplemental letter dated November 20, 2017, provided
additional information that clarified the application, did not expand
the scope of the application as originally noticed, and did not change
the NRC staff's original proposed no significant hazards consideration
determination as published in the Federal Register.
The Commission's related evaluation of the amendment is contained
in a Safety Evaluation dated April 17, 2018.
No significant hazards consideration comments received: No.
PSEG Nuclear LLC and Exelon Generation Company, LLC, Docket Nos. 50-272
and 50-311, Salem Nuclear Generating Station, Unit Nos. 1 and 2, Salem
County, New Jersey
Date of amendment request: September 27, 2017.
Brief description of amendments: The amendments relocated the
Reactor Coolant System Pressure Isolation Valve Table from the
Technical Specifications to the Technical Requirements Manual. The
amendments also removed references to the table and moved all notes and
leakage acceptance criteria from the table to the Technical
Specification surveillance requirements.
Date of issuance: April 18, 2018.
Effective date: As of the date of issuance and shall be implemented
within 60 days of issuance.
Amendment Nos.: 323 (Unit No. 1) and 304 (Unit No. 2). A publicly-
available version is in ADAMS under Accession No. ML18040A778;
documents related to these amendments are listed in the Safety
Evaluation enclosed with the amendments.
Renewed Facility Operating License Nos. DPR-70 and DPR-75: The
amendments revised the Renewed Facility Operating Licenses and
Technical Specifications.
Date of initial notice in Federal Register: November 21, 2017 (82
FR 55408).
The Commission's related evaluation of the amendments is contained
in a Safety Evaluation dated April 18, 2018.
No significant hazards consideration comments received: No.
PSEG Nuclear LLC and Exelon Generation Company, LLC, Docket Nos. 50-272
and 50-311, Salem Nuclear Generating Station, Unit Nos. 1 and 2, Salem
County, New Jersey
Date of amendment request: February 8, 2018.
Brief description of amendments: The amendments modified the Salem
Nuclear Generating Station, Unit Nos. 1 and 2, Technical Specification
(TS)-allowed outage time for more than one inoperable analog rod
position indicator
[[Page 20866]]
from 1 hour to 24 hours and changed the basis for entry into the TS
actions for inoperable rod position indicators from ``per bank'' to
``per group.'' The amendments also separated existing TS 3.1.3.2.1,
Action a.1, into two separate actions and removed the duplicative
Action b (Unit No. 1 only).
Date of issuance: April 18, 2018.
Effective date: As of the date of issuance and shall be implemented
within 30 days from the date of issuance.
Amendment Nos.: 324 (Unit No. 1) and 305 (Unit No. 2). A publicly-
available version is in ADAMS under Accession No. ML18085B198;
documents related to these amendments are listed in the Safety
Evaluation enclosed with the amendments.
Renewed Facility Operating License Nos. DPR-70 and DPR-75: The
amendments revised the Renewed Facility Operating Licenses and TSs.
Date of initial notice in Federal Register: March 1, 2018 (83 FR
8904).
The Commission's related evaluation of the amendments is contained
in a Safety Evaluation dated April 18, 2018.
No significant hazards consideration comments received: No.
PSEG Nuclear LLC, Docket No. 50-354, Hope Creek Generating Station
(HCGS), Salem County, New Jersey
Date of amendment request: November 9, 2017, as supplemented by
letter dated January 22, 2018.
Brief description of amendment: The amendment revised the HCGS
Technical Specifications. Specifically, the amendment revised the
safety limit minimum critical power ratio for two recirculation loop
operation and single recirculation loop operation based on the HCGS
Cycle 22 specific analysis.
Date of issuance: April 11, 2018.
Effective date: As of the date of issuance and shall be implemented
prior to startup following the spring 2018 refueling outage.
Amendment No.: 211. A publicly-available version is in ADAMS under
Accession No. ML18081A044; documents related to this amendment are
listed in the Safety Evaluation enclosed with the amendment.
Renewed Facility Operating License No. NPF-57: The amendment
revised the renewed facility operating license and technical
specifications.
Date of initial notice in Federal Register: February 6, 2018 (83 FR
5281). The supplemental letter dated January 22, 2018, provided
additional information that clarified the application, did not expand
the scope of the application as originally noticed, and did not change
the NRC staff's original proposed no significant hazards consideration
determination as published in the Federal Register.
The Commission's related evaluation of the amendment is contained
in a Safety Evaluation dated April 11, 2018.
No significant hazards consideration comments received: No.
Southern Nuclear Operating Company, Docket Nos. 52-025 and 52-026,
Vogtle Electric Generating Plant (VEGP), Unit Nos. 3 and 4, Burke
County, Georgia
Date of amendment request: September 13, 2017.
Description of amendment: The amendments authorized changes to the
VEGP, Unit Nos. 3 and 4, Updated Final Safety Analysis Report in the
form of departures from the plant-specific Design Control Document Tier
2 information and involved related changes to the VEGP, Units 3 and 4,
Combined License (COL) Appendix A, Technical Specifications.
The amendments authorized changes to the mass of trisodium
phosphate required inside containment to provide adjustment of the pH
of the water in the containment following an accident in which the
containment floods. These changes are reflected in COL Appendix A.
Date of issuance: February 27, 2018.
Effective date: As of the date of issuance and shall be implemented
within 30 days of issuance.
Amendment Nos.: 110 (Unit No. 3) and 109 (Unit No. 4). A publicly-
available version is in ADAMS under Package Accession No. ML18030A612;
documents related to these amendments are listed in the Safety
Evaluation enclosed with the amendments.
Facility Combined Licenses Nos. NPF-91 and NPF-92: Amendments
revised the facility COL.
Date of initial notice in Federal Register: November 21, 2017 (82
FR 55401).
The Commission's related evaluation of the amendments is contained
in a Safety Evaluation dated February 27, 2018.
No significant hazards consideration comments received: No.
Dated at Rockville, Maryland, this 26th day of April 2018.
For the Nuclear Regulatory Commission.
Tara Inverso,
Acting Deputy Director, Division of Operating Reactor Licensing, Office
of Nuclear Reactor Regulation.
[FR Doc. 2018-09244 Filed 5-7-18; 8:45 am]
BILLING CODE 7590-01-P